Immobilization of chloride radioactive waste using a phosphate glass composite material

The article confirms the possibility of using a two-component iron-phosphate glass composite material synthesized at 700 °C to immobilize a simulator of a highly-active spent chloride electrolyte, such as those obtained in the pyrochemical processing of the spent mixed uranium-plutonium fuel of a BREST-OD-300 reactor. The structure and phase composition of the material were studied using scanning electron microscopy with energy-dispersion X‑ray spectroscopy, X‑ray fluorescence analysis, and X-ray powder diffractometry. The waste components are shown to form stable pyrophosphate phases. The material leachability of waste components is defined according to the PCT standard. The glass composite material is highly water resistant. Thus, the prospects for the practical application of the studied material for the reliable immobilization of spent electrolyte materials are demonstrated.